2021 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2L01-05] Engineering of Plasma Facing Components

Thu. Sep 9, 2021 9:30 AM - 11:00 AM Room L

chair: Kazunari Katayama (Kyushu Univ.)

10:00 AM - 10:15 AM

[2L03] Plasma driven permeation behavior of hydrogen isotope in tungsten under H-D-He mixed plasma exposure

*Kyosuke Ashizawa1, Yuki Koyama1, Shiori Hirata1, Naoko Ashikawa2, yoji someya3, Yuji Hatano4, Yasuhisa Oya1 (1. Shizuoka Univ., 2. NIFS・SOKENDAI, 3. QST, 4. Univ. of Toyama)

Keywords:Tungsten, Plasma driven permeation, Irradiation defects, H-D-He mixture plasma

The influence of H and He on D plasma driven permeation (PDP) behavior in tungsten were studied by PDP experimental device as well as the impact of irradiation defects.
The results showed that the permeation rate of H was about 1.3 to 1.7 times as high as that of D. The H/D ratio was changed, and at H:D = 50:50, the permeation of HD was the maximum. In the H-D-He mixed exposure, the permeation flux and retention of D were decreased, indicating that the diffusion of D was suppressed by the formation of He bubbles. In this presentation, more detail experimental results related to permeation and diffusion behavior of hydrogen isotope in W will be discussed.